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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.1
- 수록면
- 1,109 - 1,112 (4page)
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초록· 키워드
오류제보하기
The precise prediction of radiation embrittlement of aged reactor pressure vessels (RPVs) is a prerequisitefor the long-term operation of nuclear power plants beyond their original design life. The expirationof the operation licenses for Korean reactors the RPVs of which are made from SA533B-1 platesand welds is imminent. Korean regulatory rules have adopted the US Nuclear Regulatory Commission'stransition temperature shift (TTS) models to the prediction of the embrittlement of Korean reactorpressure vessels. The applicability of the TTS model to predict the embrittlement of Korean RPVs made ofSA533B-1 plates and welds was investigated in this study. It was concluded that the TTS model of 10 CFR50.61a matched the trends of the radiation embrittlement in the SA533B-1 plates and welds better thandid that of Regulatory Guide (RG) 1.99 Rev. 2. This is attributed to the fact that the prediction performanceof 10 CFR 50.61a was enhanced by considering the difference in radiation embrittlement sensitivityamong the different types of RPV materials.
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등록된 정보가 없습니다.
참고문헌 (9)
참고문헌 신청
/ / https://www.gpo.gov/fdsys/pkg/CFR-2012-title10-vol1/pdf/CFR-2012-title10-vol1-sec50-61a.pdf
C. E. Carpenter / 2000 / Reactor Pressure Vessel Status Report
E. D. Eason / 2013 / A physically-based correlation of irradiation-induced transition temperature shifts for RPV Steels / J. Nucl. Mater 433 : 240 ~ 254
IAEA / 2009 / Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels
J. H. Yoon / 2015 / Development of Advanced Technology for Enhancing Long Term Operation Safety of Nuclear Materials
E. D. Eason / 2013 / A physically-based correlation of irradiation-induced transition temperature shifts for RPV Steels / J. Nucl. Mater 433 : 240 ~ 254
IAEA / 2009 / Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels
J. H. Yoon / 2015 / Development of Advanced Technology for Enhancing Long Term Operation Safety of Nuclear Materials
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